JP3092173B2 - Water supply control device for steam generation plant - Google Patents

Water supply control device for steam generation plant

Info

Publication number
JP3092173B2
JP3092173B2 JP03023112A JP2311291A JP3092173B2 JP 3092173 B2 JP3092173 B2 JP 3092173B2 JP 03023112 A JP03023112 A JP 03023112A JP 2311291 A JP2311291 A JP 2311291A JP 3092173 B2 JP3092173 B2 JP 3092173B2
Authority
JP
Japan
Prior art keywords
signal
water supply
water
feedwater
flow
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Fee Related
Application number
JP03023112A
Other languages
Japanese (ja)
Other versions
JPH04264296A (en
Inventor
稔也 鞍掛
尚司 谷川
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP03023112A priority Critical patent/JP3092173B2/en
Publication of JPH04264296A publication Critical patent/JPH04264296A/en
Application granted granted Critical
Publication of JP3092173B2 publication Critical patent/JP3092173B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Flow Control (AREA)
  • Control Of Steam Boilers And Waste-Gas Boilers (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【産業上の利用分野】本発明は、蒸気発生プラントの給
水制御装置に係り、特に、沸騰水型原子力プラントに適
用するのに好適な蒸気発生プラントの給水制御装置に関
する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a water supply control device for a steam generation plant, and more particularly to a water supply control device for a steam generation plant suitable for application to a boiling water nuclear power plant.

【0002】[0002]

【従来の技術】従来の沸騰水型原子力プラントの給水制
御装置は、特開昭57−197499号公報に示されているよう
に、原子力圧力容器内の水位(以下、原子炉水位とい
う)、給水流量及び主蒸気流量の各信号を取込み、これ
らの信号に基づいて原子炉圧力容器に供給される給水流
量を制御する。これによって、原子炉水位が所定のレベ
ルに保たれる。
2. Description of the Related Art A conventional water supply control apparatus for a boiling water nuclear power plant is disclosed in Japanese Patent Application Laid-Open No. 57-197499, which discloses a water level (hereinafter referred to as a reactor water level) in a nuclear pressure vessel and a water supply. The flow rate and main steam flow rate signals are taken in, and the feedwater flow rate supplied to the reactor pressure vessel is controlled based on these signals. As a result, the reactor water level is maintained at a predetermined level.

【0003】並列に配置した三台のモータ駆動給水ポン
プを備えた沸騰水型原子力プラントでは、二台のモータ
駆動給水ポンプが定速回転の電動機で駆動されるため、
モータ駆動給水ポンプ吐出側に設けられた給水調節弁の
開度が給水制御装置から出力された弁開度要求信号によ
って制御される。給水流量はこのようにして調整され
る。
In a boiling water nuclear power plant equipped with three motor-driven water supply pumps arranged in parallel, two motor-driven water supply pumps are driven by a constant-speed motor.
The opening of the water supply control valve provided on the discharge side of the motor-driven water supply pump is controlled by a valve opening request signal output from the water supply control device. The feedwater flow rate is adjusted in this way.

【0004】このような沸騰水型原子力プラントにおい
て、選択制御棒(SRI)の挿入等により原子炉水位低
下が発生した場合、同じ反応度の投入量であってもSR
Iのパターンにより、図4の実線のように−15cm程度
の水位低下になるケース、及び図4の破線のように−4
0cm程度の水位低下となる場合がある。
[0004] In such a boiling water nuclear power plant, when the reactor water level drops due to the insertion of a selective control rod (SRI) or the like, even if the input amount has the same reactivity, the SR
The pattern I results in a water level drop of about −15 cm as shown by the solid line in FIG. 4 and −4 cm as shown by the broken line in FIG.
The water level may drop by about 0 cm.

【0005】前者の場合では、水位低下に合わせて給水
制御装置11により給水調節弁が開けられ、給水流量が
一時的に110%まで増加する。しかし、原子炉水位の
回復に伴って給水流量も低下する。
In the former case, the water supply control valve 11 is opened by the water supply control device 11 in accordance with the decrease in the water level, and the water supply flow rate temporarily increases to 110%. However, as the reactor water level recovers, the feedwater flow rate also decreases.

【0006】後者の場合では、給水流量は、破線が示す
ように、給水制御装置の出力信号により、初期の原子炉
水位の低下に伴って増加し、約135%まで達する。こ
の時、給水ポンプはランアウト状態となっており、給水
ポンプが破損する可能性があった。
In the latter case, as indicated by the broken line, the feedwater flow rate increases with the initial reactor water level drop and reaches about 135% by the output signal of the feedwater control device. At this time, the water supply pump was in a run-out state, and the water supply pump could be damaged.

【0007】[0007]

【発明が解決しようとする課題】上記従来技術は、給水
ポンプのランアウト保護及び過負荷防止の点について考
慮されておらず、選択制御棒挿入等により、原子炉水位
が低下する事象が発生した場合に、給水流量を増加させ
過ぎるためランアウト流量を越える可能性があった。
The above prior art does not take into consideration the run-out protection and overload prevention of the feedwater pump, and when the reactor water level drops due to selective control rod insertion or the like. In addition, there was a possibility that the flow rate would exceed the run-out flow rate due to excessive increase in the feed water flow rate.

【0008】本発明の目的は、給水ポンプのランアウト
を防止できる蒸気発生プラントの給水制御装置を提供す
ることにある。
It is an object of the present invention to provide a water supply control device for a steam generating plant that can prevent run-out of a water supply pump.

【0009】[0009]

【0010】[0010]

【課題を解決するための手段】 上記の目的を達成する
発明の特徴は、前記給水流量信号が保護設定値以上にな
った場合にポンプ保護信号を出力する手段と、前記ポン
プ保護信号が出力されたとき、前記給水流量信号、及び
前記ポンプ保護信号が出力される前に入力した前記給水
調節弁の開度に基づいて第2給水流量制御信号を出力す
る給水流量制御手段と、前記第1給水流量制御信号と前
記第2給水流量制御信号のうち低値の給水流量信号を出
力する信号選択手段とを備え、前記信号選択手段から出
力された給水流量信号である給水調節弁開度制御信号に
基づいて前記給水調節弁を制御することにある。
Features of the present <br/> invention to achieve the above object, according to an aspect of the means for outputting a pump protection signal when said feed water flow signal is equal to or greater than the protection level, the pump When a protection signal is output, the feedwater flow rate signal, and a feedwater flow rate control unit that outputs a second feedwater flow rate control signal based on an opening degree of the feedwater control valve that is input before the pump protection signal is output, and And a signal selecting means for outputting a low value of the feed water flow signal among the first feed water flow control signal and the second feed water flow control signal, wherein the feed water control valve is a feed water flow signal output from the signal selecting means. It is to control the water supply control valve based on an opening control signal.

【0011】[0011]

【0012】発明は、ポンプ保護信号が出力されたと
き、第1給水流量制御信号より低値の第2給水流量制御
信号(給水調節弁開度制御信号)を、ポンプ保護信号が出
力される前に入力した給水調節弁の開度に基づいて得て
いる。このため、給水調節弁開度制御信号は、ポンプ保
護信号が出力された時点における、給水調節弁の実際の
開度を反映したものとなる。従って、保護設定値からの
給水流量のオーバーシュートを抑制でき、給水流量が給
水ポンプトリップ値に到達しなくなる。
According to the present invention, when the pump protection signal is output, the pump protection signal is output with a second feedwater flow control signal (feedwater control valve opening control signal) lower than the first feedwater flow control signal. It is obtained based on the previously input opening of the water supply control valve. Therefore, the water supply control valve opening control signal reflects the actual opening of the water supply control valve when the pump protection signal is output. Therefore, the overshoot of the feedwater flow from the protection set value can be suppressed, and the feedwater flow does not reach the feedwater pump trip value.

【0013】[0013]

【実施例】沸騰水型原子力プラントに適用した本発明の
好適な一実施例である蒸気発生プラントの給水制御装置
を、図1,図2及び図3に基づいて以下に説明する。沸
騰水型原子力プラントの原子炉圧力容器は蒸気発生器で
ある。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A water supply control apparatus for a steam generating plant according to a preferred embodiment of the present invention applied to a boiling water nuclear power plant will be described below with reference to FIGS. 1, 2 and 3. FIG. The reactor pressure vessel of a boiling water nuclear power plant is a steam generator.

【0014】沸騰水型原子力プラントの通常運転時にお
いて、原子炉圧力容器1内の炉心2で加熱された冷却水
は蒸気となる。この蒸気は、原子炉圧力容器1から吐出
され、主蒸気管3を通ってタービン4に送られる。ター
ビン4から排気された蒸気は、復水器5によって凝縮さ
れて水になる。復水器5から吐出された凝縮水、即ち、
原子炉の冷却水となる給水は、給水配管6により、復水
脱塩器(図示せず)、復水ポンプ7、及び給水加熱器
(図示せず)に供給される。
During normal operation of a boiling water nuclear power plant, the cooling water heated in the reactor core 2 in the reactor pressure vessel 1 becomes steam. This steam is discharged from the reactor pressure vessel 1 and sent to the turbine 4 through the main steam pipe 3. The steam exhausted from the turbine 4 is condensed by the condenser 5 into water. Condensed water discharged from the condenser 5, that is,
Supply water serving as cooling water for the reactor is supplied to a condensate demineralizer (not shown), a condensate pump 7, and a feedwater heater (not shown) by a feedwater pipe 6.

【0015】更に、給水は、給水配管6の分岐管8A,
8B,8Cに個々に設けられた三台のモータ駆動給水ポ
ンプ(MD−RFP)9A,9B,9Cのうちの二台によ
り加圧され、さらに二台の給水調節弁10A,10Bが
給水制御装置11からの弁開度指令信号12により調節
され適切な給水流量となり、原子炉圧力容器1に供給さ
れる。給水調節弁10A,10Bによる給水流量の制御
は、原子炉圧力容器1内の水位を計測する水位計13に
よる水位信号14,給水配管15に設けられた給水流量
計16による給水流量信号17、及び主蒸気配管3に設
けられた主蒸気流量計18による主蒸気流量信号19の
三要素信号により、給水流量制御装置11により制御さ
れる。
Further, water is supplied from a branch pipe 8A of the water supply pipe 6,
8B, 8C are pressurized by two of three motor-driven water supply pumps (MD-RFP) 9A, 9B, 9C provided individually, and two water supply control valves 10A, 10B are provided with water supply control devices. The water supply flow rate is adjusted by the valve opening command signal 12 from the valve 11 and is supplied to the reactor pressure vessel 1. The control of the water supply flow rate by the water supply control valves 10A and 10B includes a water level signal 14 by a water level meter 13 for measuring a water level in the reactor pressure vessel 1, a water supply flow signal 17 by a water flow meter 16 provided in a water supply pipe 15, and The feedwater flow control device 11 controls the feedwater flow control device 11 based on a three-element signal of a main steam flow signal 19 from a main steam flow meter 18 provided in the main steam pipe 3.

【0016】給水流量制御装置11は、図2に示すよう
に、三要素に基づく給水調節弁開度要求信号12を出力
する水位制御器23,ポンプ台数判定部27,給水流量
制御判定部30及び給水流量制御器36を有する。
As shown in FIG. 2, the water supply flow control device 11 outputs a water supply control valve opening request signal 12 based on three factors, a water level controller 23, a pump number determination unit 27, a water supply flow control determination unit 30, and A feedwater flow controller 36 is provided.

【0017】通常運転時における、この給水流量制御装
置11の作用を以下に説明する。主蒸気流量信号19と
給水流量信号17との偏差信号が得られる。この偏差信
号にミスマッチゲイン20がかけられて得られた信号と
原子炉水位信号14との和信号が求められる。この和信
号と原子炉水位設定信号21との偏差が、水位偏差信号
22となる。水位制御器23は、水位偏差信号22を入
力して比例積分演算を行い、給水調節弁開度要求信号1
2を出力する。低値優先回路42は、スイッチ35を介
して100%信号発生器34からの出力信号、及び給水
調節弁開度要求信号12を入力し、給水調節弁開度要求
信号12を選択して弁開度要求信号41として出力す
る。この給水調節弁開度要求信号12が、給水流量制御
装置11から出力され、給水調節弁10A,10Bを制
御する。
The operation of the water supply flow control device 11 during normal operation will be described below. A deviation signal between the main steam flow signal 19 and the feedwater flow signal 17 is obtained. A sum signal of a signal obtained by multiplying the deviation signal by the mismatch gain 20 and the reactor water level signal 14 is obtained. The difference between the sum signal and the reactor water level setting signal 21 is the water level deviation signal 22. The water level controller 23 receives the water level deviation signal 22 and performs a proportional integral operation to obtain the water supply control valve opening request signal 1.
2 is output. The low value priority circuit 42 receives the output signal from the 100% signal generator 34 and the water supply control valve opening request signal 12 via the switch 35, selects the water supply control valve opening request signal 12, and opens the valve. It is output as the degree request signal 41. The feed water control valve opening request signal 12 is output from the feed water flow control device 11, and controls the feed water control valves 10A and 10B.

【0018】ポンプ台数判定部27は、2アウトオブロ
ジックにより、給水ポンプモータ24A,24B,24
Cそれぞれの遮断器25A,25B,25Cの閉状態を
検出した信号26A,26B,26Cにより、給水ポン
プ一台運転中か二台運転中かを判定する。ポンプ台数判
定部27は、この判定により得られた一台運転信号2
9、または二台運転信号28を給水流量制御判定部30
に送る。
The number-of-pumps judging section 27 uses two out-of-logic to supply water pump motors 24A, 24B and 24.
Based on the signals 26A, 26B, and 26C that detect the closed state of each of the circuit breakers 25A, 25B, and 25C, it is determined whether one water pump is operating or two water pumps are operating. The number-of-pumps determination unit 27 determines the one-unit operation signal 2 obtained by this determination.
9 or the two-unit operation signal 28 is supplied to the feedwater flow control
Send to

【0019】給水流量制御判定部30は、図3に示すよ
うに、給水流量信号17(c)が、給水ポンプ二台運転
中に規定値Dを上回るか、或いは、給水ポンプ一台運転
中に規定値Eを上回った場合に、オアゲート31より給
水ポンプ保護信号32を出力する。給水ポンプ保護信号
32は、自己保持がかかり、給水ポンプ保護信号33と
して出力される。
As shown in FIG. 3, the feed water flow control judging section 30 determines whether the feed water flow signal 17 (c) exceeds the specified value D when two feed pumps are operating, or when the single feed pump is operating. When the value exceeds the specified value E, a water supply pump protection signal 32 is output from the OR gate 31. The feedwater pump protection signal 32 is self-maintained and is output as a feedwater pump protection signal 33.

【0020】給水ポンプ保護信号33が給水流量制御判
定部30から出力されると、スイッチ35は、通常時に
おける低値優先回路42と100%信号発生器34との
接続を、低値優先回路42と給水流量制御器36との接
続に切替える。
When the feed water pump protection signal 33 is output from the feed water flow control judging section 30, the switch 35 sets the connection between the low value priority circuit 42 and the 100% signal generator 34 in the normal state to the low value priority circuit 42. And the connection to the feedwater flow controller 36.

【0021】給水流量制御器36は、給水ポンプ台数判
定部27からの信号により選択される給水ポンプ一台運
転時(或いは二台運転時)の設定値38と給水流量信号2
7との偏差信号39を入力する。設定値38は、一台運
転信号29が出力されるときには給水ポンプ一台運転時
の設定値となり、二台運転信号28が出力されるときに
は給水ポンプ二台運転時の設定値となる。給水流量制御
器36は、偏差信号39を用いて比例・積分演算を行
い、得られた結果としての給水流量制御信号37を出力
する。
The feed water flow controller 36 is provided with a set value 38 when one feed pump is operated (or when two pumps are operated) selected by a signal from the feed water pump number judging section 27 and the feed water flow signal 2
7 is input. The set value 38 is a set value when one water supply pump is operated when the one-unit operation signal 29 is output, and is a set value when two water supply pumps are operated when the two-unit operation signal 28 is output. The feedwater flow controller 36 performs a proportional / integral operation using the deviation signal 39 and outputs a feedwater flow control signal 37 as an obtained result.

【0022】通常運転時、即ち、給水ポンプ保護信号3
3がオフの場合、給水調節弁開度検出信号52が給水流
量制御器36へタイバックされる。給水ポンプ保護信号
33がオンになると、給水調節弁開度検出信号52の給
水流量制御器36へのタイバックが停止される。このた
め、給水流量制御器36は、給水ポンプ保護信号33が
オンになった時点での給水調節弁開度検出信号52を反
映した給水流量制御信号37を出力する。給水ポンプ保
護信号33がオンになると、低値優先回路42は、給水
流量制御信号37を選択して弁開度要求信号41として
出力する。これにより、給水流量が給水ポンプ運転台数
により定まる保護設定値を上回った場合に、給水流量一
定制御が行われる。
During normal operation, that is, the feed water pump protection signal 3
When 3 is off, the feedwater control valve opening detection signal 52 is tied back to the feedwater flow controller 36. When the feedwater pump protection signal 33 is turned on, the tieback of the feedwater control valve opening detection signal 52 to the feedwater flow controller 36 is stopped. Therefore, the feedwater flow controller 36 outputs the feedwater flow control signal 37 reflecting the feedwater control valve opening detection signal 52 at the time when the feedwater pump protection signal 33 is turned on. When the feedwater pump protection signal 33 is turned on, the low value priority circuit 42 selects the feedwater flow control signal 37 and outputs it as the valve opening request signal 41. Thus, when the water supply flow rate exceeds a protection set value determined by the number of operating water supply pumps, the water supply flow rate constant control is performed.

【0023】給水調節弁10A,10Bの開度は、給水
流量制御信号37により、給水ポンプ保護信号33がオ
ンになった時点での給水調節弁開度から引き続いて制御
されることになる。このため、保護設定値からの給水流
量のオーバーシュートが抑制され、給水流量が一度も給
水ポンプトリツプ値に達することはない。
The opening of the water supply control valves 10A and 10B is controlled by the water supply flow control signal 37 continuously from the water supply control valve opening when the water supply pump protection signal 33 is turned on. For this reason, the overshoot of the feed water flow from the protection set value is suppressed, and the feed water flow never reaches the feed pump trip value.

【0024】一方、給水ポンプ保護信号33がオンの場
合に、バイアス(+10%)40が給水流量制御信号3
7に加算されて得られた積分器上限制限値43が、水位
制御器23に入力される。水位制御器23の積分器出力
の上限は、積分器上限制限値43により制限される。こ
れにより、給水ポンプ保護動作が長く続いても、水位制
御器23の積分器は飽和することがないので、原子炉水
位が回復して低値優先回路42で給水調節弁開度要求信
号12が選択された場合でも、給水調節弁開度要求信号
12による水位制御を速やかに再開できる。
On the other hand, when the feed water pump protection signal 33 is on, the bias (+ 10%) 40
The integrator upper limit value 43 obtained by being added to 7 is input to the water level controller 23. The upper limit of the integrator output of the water level controller 23 is limited by the integrator upper limit value 43. As a result, even if the feed water pump protection operation continues for a long time, the integrator of the water level controller 23 does not saturate, so that the reactor water level recovers and the low-value priority circuit 42 outputs the feed water control valve opening request signal 12. Even when it is selected, the water level control by the water supply control valve opening request signal 12 can be promptly restarted.

【0025】また、水位制御器23の出力である給水調
節弁開度要求信号12、及び低値優先回路42の出力で
ある弁開度要求信号41が、給水ポンプ保護リセット判
定部44に入力される。給水ポンプ保護リセット判定部
44は、図3に示すように、信号比較器45及びタイマ
46を有する。信号比較器45は、給水調節弁開度要求
信号12が弁開度要求信号41以下になったことを検出
し、リセット信号47を出力する。タイマ46は、入力
したリセット信号47を、この入力して約5秒経過した
後に、給水制御判定部30に対して出力する。給水制御
判定部30は、リセット信号47の入力で自己保持回路
をリセットすることにより、給水ポンプ保護信号33を
リセットする。給水制御判定部30は、給水ポンプ保護
信号33の出力を停止する。スイッチ35は100%信
号発生器34側の端子に接続される。これにより、給水
調節弁開度要求信号12による給水調節弁10A,10
Bの制御が行われる。同時に、積分器上限制限値43の
水位制御器23への入力が停止されると共に、給水調節
弁開度検出信号52が給水流量制御器36へタイバック
される。
The feed water control valve opening request signal 12 output from the water level controller 23 and the valve opening request signal 41 output from the low value priority circuit 42 are input to the feed water pump protection reset determination section 44. You. The feedwater pump protection reset determination unit 44 has a signal comparator 45 and a timer 46 as shown in FIG. The signal comparator 45 detects that the water supply control valve opening request signal 12 has become equal to or less than the valve opening request signal 41, and outputs a reset signal 47. The timer 46 outputs the input reset signal 47 to the water supply control determination unit 30 after about 5 seconds have passed after the input. The water supply control determination unit 30 resets the water supply pump protection signal 33 by resetting the self-holding circuit when the reset signal 47 is input. The water supply control determination unit 30 stops outputting the water supply pump protection signal 33. The switch 35 is connected to a terminal on the 100% signal generator 34 side. Thereby, the water supply control valves 10A, 10A based on the water supply control valve opening degree request signal 12
The control of B is performed. At the same time, the input of the integrator upper limit value 43 to the water level controller 23 is stopped, and the feed water control valve opening detection signal 52 is tied back to the feed water flow controller 36.

【0026】以下に、本実施例の作用を具体的に説明す
る。
Hereinafter, the operation of the present embodiment will be specifically described.

【0027】図5は、主蒸気隔離弁全閉時の、給水流
量,原子炉水位,制御器出力の変化を実線(従来の三要
素制御法)及び破線で示したものである。
FIG. 5 shows the changes in the feedwater flow rate, the reactor water level, and the controller output when the main steam isolation valve is fully closed by a solid line (conventional three-element control method) and a broken line.

【0028】従来の三要素制御法(実線)は、主蒸気隔
離弁閉による原子炉水位低下に対応して水位制御器にて
給水流量を約140%まで増加させている。このため、
給水ポンプ二台運転時のランアウトフロー設定値110
%を上回る。
In the conventional three-element control method (solid line), the feedwater flow rate is increased to about 140% by the water level controller in response to the reactor water level drop due to the closing of the main steam isolation valve. For this reason,
Runout flow set value 110 when two feed pumps are operated
%.

【0029】図6は、給水流量制御器のタイバック先
を、水位制御器出力信号(実線)にした場合と、給水調
節弁開度信号(破線,本実施例)にした場合の、給水流
量,原子炉水位,制御器出力の変化を示したものであ
る。
FIG. 6 shows the water supply flow rate when the tieback destination of the water supply flow rate controller is a water level controller output signal (solid line) and when the water supply control valve opening signal (dashed line, this embodiment) is used. , Reactor water level, and controller output.

【0030】水位制御器出力信号にタイバックした場合
は、給水ポンプ保護機構の作動直後の給水流量のオーバ
ーシュートが約120%に達する。なお、復水ろ過装置
及び復水脱塩装置が設置されている沸騰水型原子力プラ
ントでは、一時的に給水ポンプトリツプ値に達してい
る。
When a tieback is made to the water level controller output signal, the overshoot of the feedwater flow amount immediately after the operation of the feedwater pump protection mechanism reaches about 120%. In a boiling water nuclear power plant in which a condensate filtration device and a condensate desalination device are installed, the feedwater pump trip value is temporarily reached.

【0031】一方、本実施例では給水流量の最大値は約
114%であり、これは、給水ポンプトリツプ値117
%を下回っている。本実施例は、給水ポンプが破損する
可能性を解消できる。
On the other hand, in the present embodiment, the maximum value of the feedwater flow rate is about 114%, which is equivalent to the feedwater pump trip value 117.
%. This embodiment can eliminate the possibility that the water supply pump is damaged.

【0032】沸騰水型原子力プラントに適用した本発明
の他の実施例である上記発生プラントの給水制御装置に
ついて説明する。
A description will now be given of a water supply control device for the above-mentioned generation plant, which is another embodiment of the present invention applied to a boiling water nuclear power plant.

【0033】前述の実施例では給水流量制御器36は給
水ポンプ保護信号33が発生するまで給水調節弁開度信
号52を入力していたが、本実施例は、図7に示すよう
に、給水調節弁開度信号52を給水流量制御器36に入
力しない構成となっている。替りに、本実施例の給水流
量制御器36は、給水ポンプ保護信号33が発生するま
で、水位制御器23の出力である給水調節弁開度要求信
号12からバイアス49である偏差(5%)を差し引い
た値を、入力している。給水ポンプ保護信号33が発生
したとき、給水流量制御器36は、給水ポンプ保護信号
33が発生した時点のその値を反映した給水流量制御信
号37を出力する。
In the above-described embodiment, the feedwater flow controller 36 inputs the feedwater control valve opening signal 52 until the feedwater pump protection signal 33 is generated. In this embodiment, however, as shown in FIG. The control valve opening signal 52 is not input to the feedwater flow controller 36. Instead, the feedwater flow controller 36 of the present embodiment is a bias 49% deviation (5%) from the feedwater control valve opening request signal 12 which is the output of the water level controller 23 until the feedwater pump protection signal 33 is generated. The value after subtracting is entered. When the feedwater pump protection signal 33 is generated, the feedwater flow controller 36 outputs a feedwater flow control signal 37 reflecting the value at the time when the feedwater pump protection signal 33 is generated.

【0034】これにより、図6に示したと同様に、給水
ポンプトリツプ値に達する事を回避できる。
Thus, it is possible to avoid reaching the feedwater pump trip value as shown in FIG.

【0035】[0035]

【0036】[0036]

【発明の効果】 発明によれば、保護設定値からの給水
流量のオーバーシュートを抑制でき、給水ポンプトリッ
プの発生を回避できる。
According to the present invention, it can suppress the overshooting of feedwater flow from the protection setting value can avoid the occurrence of the water supply pump trip.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明による給水制御装置と沸騰水型原子力プ
ラント系統図。
FIG. 1 is a system diagram of a water supply control device and a boiling water nuclear power plant according to the present invention.

【図2】本発明による給水制御装置の詳細図。FIG. 2 is a detailed view of a water supply control device according to the present invention.

【図3】本発明による給水制御装置の詳細図。FIG. 3 is a detailed view of a water supply control device according to the present invention.

【図4】従来給水制御装置によるSRI挿入時のプラン
ト挙動説明図。
FIG. 4 is an explanatory view of a plant behavior when an SRI is inserted by the conventional water supply control device.

【図5】従来給水制御装置による主蒸気隔離弁閉時のプ
ラント挙動説明図。
FIG. 5 is an explanatory diagram of a plant behavior when a main steam isolation valve is closed by a conventional water supply control device.

【図6】本発明給水制御装置による主蒸気隔離弁閉時の
プラント挙動説明図。
FIG. 6 is an explanatory diagram of a plant behavior when the main steam isolation valve is closed by the water supply control device of the present invention.

【図7】本発明の他の実施例の系統図。FIG. 7 is a system diagram of another embodiment of the present invention.

【符号の説明】[Explanation of symbols]

1…原子炉圧力容器、2…炉心、4…主蒸気配管、4…
タービン、5…復水器、6,15…給水配管、7…復水
ポンプ、8A,8B,8C…給水分岐管、9A,9B,
9C…電動駆動給水ポンプ、10A,10B…給水調節
弁、11…給水制御装置、12…給水調節弁開度要求信
号、13…原子炉水位検出器、14…原子炉水位信号、
16…給水流量検出器、17…給水流量検出信号、18
…主蒸気流量検出器、19…主蒸気流量検出信号。
1 ... Reactor pressure vessel, 2 ... Core, 4 ... Main steam piping, 4 ...
Turbine, 5 ... condenser, 6, 15 ... water supply pipe, 7 ... condensate pump, 8A, 8B, 8C ... water supply branch pipe, 9A, 9B,
9C: electric drive water pump, 10A, 10B: water supply control valve, 11: water supply control device, 12: water supply control valve opening request signal, 13: reactor water level detector, 14: reactor water level signal,
16: feed water flow rate detector, 17: feed water flow rate detection signal, 18
... Main steam flow detector, 19 ... Main steam flow detection signal.

フロントページの続き (58)調査した分野(Int.Cl.7,DB名) G21D 3/04 G21D 3/08 Continuation of the front page (58) Field surveyed (Int.Cl. 7 , DB name) G21D 3/04 G21D 3/08

Claims (1)

(57)【特許請求の範囲】(57) [Claims] 【請求項1】復水器から蒸気発生器に給水を導く給水配
管と、前記給水配管に設けられた複数の給水ポンプ及び
複数の給水調節弁とを備えた蒸気発生プラントの給水制
御装置において、 蒸気発生器の水位信号、前記蒸気発生器に供給される給
水の流量信号及び前記蒸気発生器から吐出される主蒸気
の流量信号に基づいて第1給水流量制御信号を出力する
水位制御手段と、前記給水流量信号が保護設定値以上に
なった場合にポンプ保護信号を出力する手段と、前記ポ
ンプ保護信号が出力されたとき、前記給水流量信号、及
び前記ポンプ保護信号が出力される前に入力した前記給
水調節弁の開度に基づいて第2給水流量制御信号を出力
する給水流量制御手段と、前記第1給水流量制御信号と
前記第2給水流量制御信号のうち低値の給水流量信号を
出力する信号選択手段とを備え、前記信号選択手段から
出力された給水流量信号である給水調節弁開度制御信号
に基づいて前記給水調節弁を制御することを特徴とする
蒸気発生プラントの給水制御装置。
A water supply control device for a steam generation plant, comprising: a water supply pipe for guiding water supply from a condenser to a steam generator; and a plurality of water supply pumps and a plurality of water supply control valves provided in the water supply pipe. Water level control means for outputting a first feed water flow rate control signal based on a water level signal of a steam generator, a flow rate signal of feed water supplied to the steam generator, and a flow rate signal of main steam discharged from the steam generator; Means for outputting a pump protection signal when the feedwater flow signal is equal to or greater than a protection set value, and when the pump protection signal is output, the feedwater flow signal, and the input before the pump protection signal is output. A feedwater flow control means for outputting a second feedwater flow control signal based on the opening degree of the feedwater control valve, and a feedwater flow signal having a low value among the first feedwater flow control signal and the second feedwater flow control signal. Water supply control for a steam generation plant, comprising: a signal selection means for outputting the water supply control valve based on a water supply control valve opening control signal that is a water supply flow rate signal output from the signal selection means. apparatus.
JP03023112A 1991-02-18 1991-02-18 Water supply control device for steam generation plant Expired - Fee Related JP3092173B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP03023112A JP3092173B2 (en) 1991-02-18 1991-02-18 Water supply control device for steam generation plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP03023112A JP3092173B2 (en) 1991-02-18 1991-02-18 Water supply control device for steam generation plant

Publications (2)

Publication Number Publication Date
JPH04264296A JPH04264296A (en) 1992-09-21
JP3092173B2 true JP3092173B2 (en) 2000-09-25

Family

ID=12101400

Family Applications (1)

Application Number Title Priority Date Filing Date
JP03023112A Expired - Fee Related JP3092173B2 (en) 1991-02-18 1991-02-18 Water supply control device for steam generation plant

Country Status (1)

Country Link
JP (1) JP3092173B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5639808B2 (en) * 2010-07-27 2014-12-10 日立Geニュークリア・エナジー株式会社 Reactor water supply controller
CN111951988B (en) * 2020-07-13 2023-03-14 中广核核电运营有限公司 Method and device for detecting abnormity of main water supply flow and computer equipment

Also Published As

Publication number Publication date
JPH04264296A (en) 1992-09-21

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